ML20059E268
| ML20059E268 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood, Zion, LaSalle File:ZionSolutions icon.png |
| Issue date: | 12/30/1993 |
| From: | Dyer J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20059E252 | List: |
| References | |
| NUDOCS 9401110060 | |
| Download: ML20059E268 (29) | |
Text
.
p "co, ff UNITED STATES jflh).&j NUCLEAR REGULATORY COMMISSION
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WASHINGTON, D.C. 20555-0001 ggv f
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COMMONWEALTH EDISON COMPANY DOCKET N0. STN 50-454 BYRON STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 57 License No. NPF-37 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated November 10, 1993, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and t
E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-37 is hereby amended to read as follows:
9401110060 931230 PDR ADOCK 05000295 p
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1 (2)
Technical Specifications The Technical Specifications contained in-Appendix A as revised through Amendment No. 57 and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of the date of its issuance.
f FOR THE NUCLEAR REGULATORY COMMISSION ~
12-M S.$lf W James E. Dyer, Director Project Directorate 111-2 Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications i
Date of Issuance: December 30, 1993 l
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,g,.m....f COMMONWEALTH EDISON COMPANY DOCKET NO. STN 50-455 BYRON STATION. UNIT 2 AME;4DMENT TO FACillTY OPERATING LICENSE Amendment No. 57 License No. NPF-66 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated November 10, 1993, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance rf this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR 4
Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-65 is hereby amended to read as follows:
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Technical Specifications The Technical Specifications contained in Appendix A (NUREG-lll3),
as revised through Amendment No. 57 and revised by Attachment 2 to NPF-66, and the Environmental Protection Plan contained. in Appendix B, both of which were attached to License No. NPF-37,-
dated February 14, 1985, are hereby incorporated into this license. Attachment 2 contains a revision to Appendix A which is.
hereby incorporated into this license.. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION 4rl4 t.
DV James E. Dyer, Director i
Project Directorate III-2 Division of Reactor Projects - III/IV/V l
Office of Nuclear Reactor Regulation.
Attachment:
Changes to the Technical i
Specifications Date of Issuance:
December 30, 1993 l
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ATTACHMENT TO LICENSE AMENDMENT N05.- 57 AND 57
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FACILITY OPERATING tlCENSE N05 NPF-37 AND NPF-66 l
DOCKET NOS. STN 50-454 AND STN 50-455 Revise the Appendix A Technical Specifications by removing the pages
. identified below and inserting the attached pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.
Remove Paaes Insert Paaes 6-18 6-18 6-19 6-19 i
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I ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued) 2)
Identification of the procedures used to measure the values of the critical variables, 3)
Identification of process sampling points, which shall include monitoring the discharge of the condensate pumps for evidence of condenser in-leakage, 4)
Procedures for the recording and management of data, 5)
Procedures defining corrective action for all off-control point chemistry conditions, and i
6)
A procedure identifying: (a) the authority responsible for the interpretation of the data, and (b) the sequence and timing of administrative events required to initiate corrective action.
d.
Post-accident Samplina A program which will ensure the capability to obtain and analyze reactor coolant, radioactive iodines and particulates in plant gaseous effluents, and containment atmosphere samples under accident conditions.
The program shall include the following:
1)
Training of personnel, 2)
Procedures for sampling and analysis, and 3)
Provisions for maintenance of sampling and analysis equipment.
e.
Radioactive Effluent Controls Proaram A program shall be provided conforming with 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to MEMBERS OF THE PUBLIC from radioactive effluents as low as
~
reasonably achievable. The program (1) shall be contained in the ODCM, (2) shall be implemented by station procedures, and (3) shall include remedial actions to be taken whenever the program limits are exceeded.
The program shall include the following elements:
1)
Limitations on the operability of radioactive. liquid and gaseous monitoring instrumentation' including surveillance tests and setpoint determination in accordance with the methodology in the ODCM, 2)
Limitations on the concentrations of radioactive material released in liquid effluents to UNRESTRICTED AREAS conforming to 10 times the concentration values in Appendix B, Table 2, Column 2 to 10 CFR 20.1001-20.2402, 3)
Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.1302 and with l
the methodology and parameters in t'se ODCM, BYRON - UNITS 1 & 2 6-18 AMENDMENT NO. 57
'4
^ ADMIN 1STRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued) 4)
Limitations on the annual and quarterly doses or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released from each unit to UNRESTRICTED AREAS.
conforming to Appendix I to 10 CFR Part 50, 5)
Determination of cumulative and projected dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology-and parameters in the ODCM at least every 31 days, 6)
Limitations on the operability and use of the liquid and gaseous effluent treatment systems to ensure that the appropriate portions of these systems are used to reduce releases of radioactivity when the projected doses in a 31-day period would exceed 2 percent of the guidelines for the annual dose or dose commitment conforming to Appendix I to 10 CFR Part 50, 7)
Limitations on the dose rate resulting from radioactive materials released in gaseous effluents-from the site to areas at or beyond the SITE BOUNDARY shall be limited to the following:
a)
For noble gases:
less than or equal to a dose rate of 500 mrem /yr to the whole body and less than or equal to a dose rate of 3000 mrem /yr to the skin, and i
b)
For Iodine-131, Iodine-133, tritium, and for all radionuclides in particulate form with half-lives greater than 8 days:
less than or equal to a dose rate of 1500 mrem /yr to any organ, 8)
Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from each unit to areas beyond the SITE B0UNDARY conforming to Appendix I to 10 CFR Part 50, 9)
Limitations on the annual and quarterly dose: to a MEMBER OF THE PUBLIC from Iodine-131, Iodine-133, half-lives greater than tritium, and all radionuclides in particulate form with 8 days in gaseous effluents released from each unit to areas beyond the SITE BOUNDARY conforming to Appendix I to 10 CFR Part 50, and
- 10) Limitations on the annual dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from I
uranium fuel cycle sources conforming to 40 CFR Part 190.
f.
Radioloaical Environmental Monitorina Proaram j
A program shall be provided to monitor the radiation and radionuclides in the environs of the plant. The rogram shall provide (1)l exposure represen-tative measurements of radioactivit in the highest potentia pathways, and (2) deling of environmental exposure pathways. verification of t e a ing program and mo The -
r program shall (1)10 CFR Part.50, and (3) inc[lude the following: guidance be contained in the ODCM,
- 2) conform to the of Appendix I to 1)
Monitoring, sampling, analysis, and reporting of radiation and radionuclides in the environment in accordance with the methodology and parameters in the ODCM, b
BYRON - UNITS 1 & 2 6-19 AMENDMENT N0. 57 r
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%,.....f COMMONWEALTH EDISON COMPANY DOCKET NO. STN 50-456 BRAIDWOOD STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 45 License No. NPF-72 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated November 10, 1993, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be. inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-72 is hereby amended to read as follows:
'l
i L
! (2)
Technical Specifications The_ Technical Specifications contained in Appendix A as revised through Amendment No. 45 and the Environmental Protection Plan j
contained in Appendix B, both of which are attached hereto, are 1
hereby incorporated into this license.
The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of the date of its issuance.
j FOR THE NUCLEAR REGULATORY COMMISSION
- JrlL {. l fGV James E. Dyer, Director Project Directorate III-2 Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation q
Attachment:
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Changes to the Technical Specifications l
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i COMMONWEALTH EDISON COMPANY DOCKET NO. STN 50-457 BRAIDWOOD STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 45 License No. NPF-77 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated November 10, 1993, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the att chment to this license amendment, and i
paragraph 2.C.(2) of Facility Operating License No. NPF-77 is hereby amended to read as follows:
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Technical Specifications The Technical Specifications contained in Appendix A as revised f
through Amendment No. 45 and the Environmental Protection Plan contained in Appendix B, both of which were attached to License No. NPF-72, dated July 2,1987, are hereby incorporated into this.
license. The licensee shall operate the facility in accordance
)
with the Technical Specifications and the En/ironmental Protection Plan.
I 3.
This license amendment is effective as of the date if its issuance.
FOR THE NUCLEAR REGULATORY' COMMISSION-1 Ullt f. ( ' f1' f
ames E. Dyer, Director l
Project Directorate III-2 Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: December 30, 1993 t
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ATTACHMENT TO LICENSE AMENDMENT NOS. 45 AND 45 FACILITY OPERATING LICENSE NOS NPF-72 AND NPF-77 DOCKET NOS. STN 50-456 AND STN 50-457 Replace the following pages of the Appendix "A" Technical' Specifications with
-l the attached pager. The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
Remove Paaes Insert Paaes-6-18 6-18 6-19 6-19
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t s
Ei i
I
-ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued) 2)
Identification of the procedures used to measure the values of the critical variables, 3)
Identification of process sampling points, which shall include monitoring the discharge of the condensate pumps for evidence of condenser in-leakage, 4)
Procedures for the recording and management of data, 5)
Procedures defining corrective action for all off-control point chemistry conditions, and 6)
A procedure identifying: (a) the authority responsible for the interpretation of the data, and (b) the sequence and timing of ddministrative events required to initiate Corrective action.
d.
Post-accident Samnlina A program which will ensure the capability to obtain and analyze reactor coolant, radioactive iodines and particulates in plant gaseous effluents, and containment atmosphere samples under accident conditions.
The program shall include the following:
1)
Training of personnel, 2)
Procedures for sampling and analysis, and 3)
Provisions for maintenance of sampling and analysis equipment.
e.
Radioactive Effluent Controls Proaram A program shall be provided conforming with 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to MEMBERS OF THE PUBLIC from radioactive effluents as low as reasonably achievable. The program (1) shall be contained in the ODCM, (2) shall be implemented by station procedures, and (3) shall include remedial actions to be taken whenever the program limits are exceeded. The program shall include the following elements:
1)
Limitations on the operability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the ODCM, 2)
Limitations on the concentrations of radioactive material released in liquid effluents to ' UNRESTRICTED AREAS conforming J
to 10 times the concentration values in Appendix B, Table 2, Column 2 to 10 CFR 20.1001-20.2402, 3)
Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.1302 and with l.
the methodology and parameters in the ODCM, i
BRAIDWOOD - UNITS 1 & 2 6-18 AMENDMENT N0. 45 j
ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued) 4)
Limitations on the annual and quarterly doses or dose connitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents releaseo from each unit to UNRESTRICTED AREAS conforming to Appendix I to 10 CFR Part 50, 5)
Determination of cumulative and projected dose contributions from radioactive effluents for the current calendar guarter and current calendar year in accordance with the methodology and parameters in the ODCM at least every 31 days, 6)
Limitations on the operability and use of the liquid and gaseous effluent treatment systems to ensure that the appropriate portions of these systems are used to reduce releases of radioactivity when the projected doses in a 31-day period would exceed 2 percent of the guidelines for the annual dose or dose commitment conforming to Appendix I to 10 CFR Part 50, 7)
Limitations on the dose rate resulting from radioactive materials released in gaseous effluents from the site to areas at or beyond the SITE BOUNDARY shall be limited to the following:
a)
For noble gases:
less than or equal to a dose rate of 500 mrem /yr to the whole body and less than or equal to a dose rate of 3000 mrem /yr to the skin, and b)
For Iodine-131 Iodine-133, tritium and for all radionuclides In particulate form with half-lives greater than 8 days:
less than or equal to a dose rate of 1500 mrem /yr to any organ, 8)
Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from each unit to areas beyond the SITE BOUNDARY conforming to Appendix I to 10 CFR Part 50, 9)
Limitations on the annual and quarterly doses to a MEMBER OF THE PUBLIC from Iodine-131, Iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released from each unit to areas beyond the SITE BOUNDARY conforming to Appendix I to 10 CFR Part 50, and 10)
Limitations on the annual dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources conforming to 40 CFR Part 190.
f.
Radiolooical Environmental Monitorina Proaram A program shall be provided to monitor the radiation and radionuclides in the environs of the plant.
The program shall provide (1) representative measurements of radioactivity in the highest potential exposure pathways, and (2) verification of the accuracy of the effluent monitoring program and modeling of environmental exposure pathways.
The program shall in the ODCM, (2) conform to the guidance of Appendix (1) be contained I to 10 CFR i
Part 50, and (3) include the following:
1)
Monitoring, sampling, analysis, and reporting of radiation'and radionuclides in the environment in accordance with the methodology and parameters in the ODCM, BRAIDWOOD - UNITS 1 & 2 6-19' AMENDMENT NO. 45
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[kpmag}t UNITED STATES yI j
NUCLEAR REGULATORY COMMISSION g.3 g
WASHINGTON. D.C 20555-0001
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I COMMONWEALTH EDISON COMPANY DOCKET NO. 50-373 LASALLE COUNTY STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 93 License No. NPF-ll 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment filed by the Commonwealth Edison Company (the licensee), dated November 10, 1993, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the regulations of the Commission; C.
There is reasonable assurance: (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations. set forth in 10 CFR Chapter I; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and
)
E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical I
Specifications' as indicated in the enclosure to this license amendment and paragraph 2.C.(2) of the f acility Operating License No. NPF-ll-is hereby amended to read as follows*
1 I
. (2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in _ Appendix A, as revised through Amendment No. 93, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This amendment is effective upon date of issuance.
[
FOR THE NUCLEAR REGULATORY COMMISSION f)!ds N.($ ev f
James E. Dyer, Director Project Directorate III-2 Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
December 30, 1993 t
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l ATTACHMENT TO LICENSE AMENDMENT NO. 93 e
FACI'.lTY OPERATING LICENSE NO. NPF-11 i
DOCKET NO. 50-373 i
Replace the following page of the Appendix "A" Technical Specifications-with the enclosed page. The revised page is identified by amendment number and' contains vertical lines indicating the area of change.
REMOVE INSERT i
6-19 6-19 i
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1 i
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.__.,___._-...--.__m
ADMINISTRATIVE CONTROLS PLANT OPERATING PROCEDURES AND PROGRAMS (Continued) i 4.
Radioactive Effluent Controls Proaram A program shall be provided conforming with 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to MEMBERS OF THE PUBLIC from radioactive effluents as low as reasonably achievable. The program 1 shall be contained in the.0DCM, (2) shall be implemented by op(er)ating procedures, and (3) shall include remedial actions to be taken whenevcr the program limits are exceeded. The program shall include the following elements:
a.
Limitations on the operability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and set-point determination in accordance with the methodology in the
- ODCM, b.
Limitations on the concentrations of radioactive material released in liquid effluents to UNRESTRICTED AREAS conforming to 10 times the concentration values in Appendix B, Table 2, Column 2 to 10 CFR 20.1001-20.2402, Monitoring,luents in accordance with 10 CFR 20.1302 sampling, and analysis of rad c.
gaseous eff and with the l
methodology and parameters in the ODCM, d.
Limitations on the annual and quarterly doses or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released from each unit to UNRESTRICTED AREAS conform-ing to Appendix 1 to 10 CFR Part 50, I
e.
Determination of cumulative and projected dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM at least'every 31 days, I
f.
Limitations on the operability and use of the liquid and gaseous effluent treatment systems to ensure that the appropriate portions of these systems are used to reduce releases of radioactivity when the projected doses in a 31-day period would exceed 2 percent of the guidelines for the annual dose or dose commitment conforming to Appendix I to 10 CFR Part 50, g.
Limitations on the dose rate re:ulting from radioactive materials released in gaseous effluents from the site to areas at or beyond the SITE BOUNDARY shall be limited to the following:
1.
For noble gases:
less than or equal to a dose rate of 500 mrem /yr to the whole body and less than or equal to a dose rate of 3000 mrem /yr to the skin, and i
2.
For Iodine-131, Iodine-133, tritium, and for all radionuclides in particulate form.a th half-lives greater than 8 days:
less than or equal to a dose rate of 1500 mrem /yr to any organ, h.
Limitations on the annual and quarterly air' doses resulting from noble gases released in gaseous effluents from each unit to areas beyond the SITE BOUNDARY conforming to Appendix I to 10 CFR Part 50, i
l LA SALLE - UNIT 1 6-19 Amendment No. 93
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l COMMONWEALTH EDISON COMPANY i
DOCKET NO. 50-374 LASALLE COUNTY STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING llCENSE l
Amendment No. 77 l
License No. NPF-18 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The appl: ation for amendment filed by the Commonwealth Edison Company (the licensee), dated Novembe.r 10, 1993, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations set forth in 10 CfR Chapter I; B.
The f acility will operate in conformity with the application, the provisions of the Act, and the regulations of the Commission; C.
There is reasonable assurance: (i) that the activities authorized by this amendment can be conduct " without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the enclosure to this license amendment and paragraph 2.C.(2) of the facility Operating License No. NPF-18 is hereby amended to read as follows:
ar
. (2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 77, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.
The licensee shall operate the facility -in accordance with the-Technical Specifications and the Environmental Protection Plan.
3.
This amendment. is effective upon date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION fMk$.$0V f
James E. Dyer, Director Droject Directorate 111-2 Division of Reactor Projects - I!!/lV/V-Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: December 30, 1993 l
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ATTACHMENT TO llCENSE AMENDMENT NO. 77 FACILITY OPERATING llCENSE NO. NPF-18 DOCKET NO. 50-374 Replace the following page of the Appendix "A" Technical Specifications with the enclosed page. The revised page is identified by amendment number and contains vertical lines indicating the area of change.
REMOVE INSERT 6-19 6-19 l
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- qw 4
ADMINISTRATIVE CONTROLS-l PtANT OPERATING PROCEDURES AND PROGRAMS (Continued) 4.
Radioactive Effluent Controls Proorg A program shall be provided conforming with 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to MEMBERS OF THE PUBLIC from radioactive effluents as low as reasonably achievable. The program (1) shall be contained in the ODCM, (2) shall be implemented by operating procedures, and (3 shall include i
remedial actions to be taken whenever the program lim)its are o
exceeded.
The program shall include the following elements:
a.
Limitations on the operability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and set-point determination in accordance with the methodology in the
- ODCM, b.
Limitations on the concentrations of radioactive material released in liquid effluents to UNRESTRICTED AREAS conforming to 10 times the concentration values in Appendix B, Table 2, Column 2 to 10 CFR 20.1001-20.2402, i
Monitoring,luents in accordance with 10 CFR 20.1302 sampling, and analysis of rad c.
gaseous eff and with the l
t methodology and parameters in the ODCM, d.
Limitations on the annual and quarterly doses or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid i
effluents released from each unit to UNRESTRICTED AREAS conform-ing to Appendix I to 10 CFR Part 50, i
e.
Determination of cumulative and projected dose contributions from radioactive effluents for the current calendar quarter and r
current calendar year in accordance with the methodology and parameters in the ODCM at least every 31 days, j
f.
Limitations on the operability and use of the liquid and gaseous effluent treatment systems to ensure that the appropriate portions of these systems are used to reduce releases of radioactivity when the projected doses in a 31-day period would exceed 2 percent of the guidelines for the annual dose or dose commitment conforming to Appendix I to 10 CFR Part 50, g.
Limitations on the dose rate resulting from radioactive materials released in gaseous effluents from the site to areas at or beyond the SITT B0UNDARY shall be limited to the following:
1.
For noble gases:
less than or equal to a dose rate of 500 mrem /yr to the whole body and less than or equal to a dose
' ate of 30cd mrem /yr to the skin, and i
2.
For Iodine-131, Iodine-133, tritium, and for all radionuclides in particulate form with half-lives greater than 8 days:
less than or equal to a dose rate of 1500 mrem /yr to any organ,
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Limitations on the annual and quarterly air doses resulting from-noble gases released in gaseous effluents from each unit to areas beyond the SITE BOUNDARY conforming to Appendix'I to 10 CFR Part 50,
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LA SALLE - UNIT 2 6-19 Amendment No. 77
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t UNITED STATES y ',J JJ "j
NUCLEAR REGULATORY COMMISSION r
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COMMONWEALTH EDISON COMPANY DOCKET NO. 50-295 ZION NUCLEAR POWER STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 152 License No. DPR-39 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated November 10, 1993, complies'with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be Tonducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2 Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-39 is hereby amended to read as follows:
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(2)
Technical Specifications
.i The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 152, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION jwe fdysv James E. Dyer, Director Project Directorate 111-2 Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: December 30, 1993 1
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UNITED STATES E Y'19[( I E h
NUCLEAll REGULATORY COMMISSION E
WASHINGTON, D.C. 20555-0001 Q g%
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COMMONWEALTH EDISON COMPANY DOCKET NO. 50-304 ZION NUCLEAR POWER STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 140 License No. DPR-48 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated November 10, 1993, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
lhe issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-48 is hereby amended to read as follows:
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1 (2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 140, are hereby incorporated in the license. The licensee shall operate the facility in accordance-with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION i
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James E. Oyer, Director Project Directorate 111-2 Division of Reactor Projects - Ill/IV/V l
Office of Nuclear Reactor Regulation
Attachment:
' Changes to the Technical Specifications Date of Issuance: December 30, 1993 r
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Y ATTACHMENT TO LICENSE AMENDMENT NOS. 152 AND 140 FACILITY OPERATING LICENSE NOS. DPR-39 AND DPR-48 DOCKET NOS. 50-295 AND 50-304 Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages. The revised pages are i
identified by the captioned amendment number and contain marginal lines indicating the area of change.
Remove Paaes Insert Paaes 310a 310a 310b 310b 4
6
.o 6.2 (Continued) 5.
Drills of the emergency procedures described in Specification 6.2.1.D shall be conducted at the frequency specified in the Generating Station Emergency Plan.
These drills will be planned so that during the course of the year, communication links are tested and outside agencies are contacted.
6.
The following programs shall be established, implemented, and maintained:
A.
Radioactive Effluent Controls Program A program shall be provided conforming with 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to MEMBERS OF THE PUBLIC from radioactive effluents as low as reasonably achievable. The program (1) shall be contained in the 00CM, (2) shall be implemented by station procedures, and (3) shall include remedial actions to be taken whenever the program limits are exceeded.
The program shall include the following elements:
1)
Limitations on the operability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the
- ODCH, 2)
Limitations on the concentrations of radioactive material released in liquid effluents to UNRESTRICTED AREAS conforming to 10 times the concentration values in Appendix B, Table 2, Column 2 to 10 CFR 20.1001-20.2402, 3)
Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.1302 and with the methodology and parameters in the ODCM, l
4)
Limitations on the annual and quarterly doses or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released from each unit to UNRESTRICTED AREAS conforming to Appendix I to 10 CFR Part 50, 5)
Determination of cumulative and projected dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM at least every 31 days, 6)
Lir,itations on the operability and use of the liquid and gaseous effluent treatment systems to er.sure that the appropriate portions of these systems are used to reduce releases of radioactivity when the projected doses in a 31-day period would exceed 2 percent of the guidelines for the annual dose or dose commitment conforming to Appendix 1 to 10 CFR Part 50, 310a Amendment Nos. 152 and 140
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6.2 (Continued) aseous effluent-k Limitations on the dose rate resultina from radioactive materials released in following:
7) from the site to areas at or beyond tfie SITE BOUNDARY shall be limited to the a) For noble gases:
less than or equal to a dose rate of 500 mrem /yr to the whole body and less than or equal to a dose rate of 3000 mrem /yr to the skin, and b) For Iodine-131, lodine-133, tritium, and for all radionuclides in particulate form with half-lives greater than 8 days:
less than or equal to a dose rate of 1500 mrem /yr to any organ, 8)
Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from each unit to areas beyond the SITE BOUNDARY conforming to Appendix I to 10 CFR Part 50, 9)
Limitations on the annual and quarterly doses to MEMBER OF THE PUBLIC from Iodine-131, Iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released from each unit to areas beyond the SITE BOUNDARY conforming to Appendix I to 10 CFR Part 50, 10)
Limitations on the annual dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources conforming to 40 CFR Part 190.
- 8. Radioloaical Environmental Monitorino Proaram A program shall be provided to monitor the radiation and radionuclides in the environs of the plant. The program shall provide (1) representative measurements of radioactivity in the highest potential exposure pathways, and (2) verification of the accuracy of the effluent monitoring program and modeling of environmental exposure pathways. The program shall (1) be contained in the ODCM, (2) conform to the guidance of Appendix I to 10 CFR Part 50, and (3) include the following:
1)
Monitoring, sampling, analysis, and reporting of radiation and radionuclides in the environment in accordance with the methocology and parameters in the ODCM, 2)
A Land Use Census to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the monitoring program are made if required by the results of this census, and 3)
Participation in a Interlaboratory Comparison Program to ensure that independent checks on the precision and accuracy of the measurements or radioactive materials in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring.
6.3 Action to be Takan in the Event of a Reportable Event in Plant Operation:
Any Reportable Event shall be promptly reported to the Vice President PWR Operations or his designated alternate.
The incident shall be promptly reviewed pursuant to Specification 6.1.7.B.2.(k}R 50.73.and a separate report for each reportable event shall be prepared in accordance with the requirements of 10 C.
310b Amendment Nos. 152 and 140
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